Study of Shielding Material and Position Optimization of Micro-CT by Monte-carlo Simulation

몬테카를로 시뮬레이션을 통한 micro-CT의 차폐 물질 및 위치 최적화 연구

  • Kim, Giyoon (Department of Nuclear & Quantum Engineering, KAIST) ;
  • Kim, Myungsoo (Department of Nuclear & Quantum Engineering, KAIST) ;
  • Kim, Minhwan (Department of Nuclear & Quantum Engineering, KAIST) ;
  • Lee, Eunjung (Department of Nuclear & Quantum Engineering, KAIST) ;
  • Cho, Gyuseong (Department of Nuclear & Quantum Engineering, KAIST)
  • 김기윤 (한국과학기술원 원자력 및 양자공학과) ;
  • 김명수 (한국과학기술원 원자력 및 양자공학과) ;
  • 김민환 (한국과학기술원 원자력 및 양자공학과) ;
  • 이은중 (한국과학기술원 원자력 및 양자공학과) ;
  • 조규성 (한국과학기술원 원자력 및 양자공학과)
  • Received : 2018.03.05
  • Accepted : 2018.06.04
  • Published : 2018.06.30

Abstract

Shielding radiation devices is a very important factor in securing the safety of users. In general, the best method of shielding radiation is to make the shielding material thick enough to minimize the amount of radiation leakage. However, since the shielding materials are very heavy, it would be necessary to consider the mass of the total system with a sufficient shielding structure for mobile systems. In this study, we investigate different materials for shielding of mobile micro-CT and evaluate the shielding performance with respect to the shielding position and the total weight of the system. The purpose of the shielding materials optimization is to compare the shielding ability with respect to the weight of the shielding material and to select the material that is sufficiently light while maximizing the shielding effect. The shield location measurement is based on the amount of leakage radiation when the shield is installed inside and outside of the micro-CT system housing. The materials used in this study are lead and tungsten with thicknesses ranging from 1 mm to 5 mm. Tungsten showed the same shielding performance at half of the lead thickness with the density less than twice the density of lead, making the tungsten shielding much lighter. In case of the shielding position, the inner shielding of the housing showed a higher shielding performance when compared to that of the outer housing.

Keywords

Acknowledgement

Supported by : Korea Science and Engineering Foundation(KOSEF)

References

  1. 김기정, 심재구. 2017. 몬테카를로 시뮬레이션을 이용한 차폐체 원소 평가. 방사선기술과학 40:269-274.
  2. Kim SC, Dong KR and Chung WK. 2012. Medical radiation shielding effect by composition of barium compounds. Ann. Nucl. Energy 47:1-5. https://doi.org/10.1016/j.anucene.2012.04.014
  3. McCaffrey JP, Shen H, Downton B and Mainegra-Hing E. 2007. Radiation attenuation by lead and nonlead materials used in radiation shielding garments. Med. phys. 34(2):530-537. https://doi.org/10.1118/1.2426404
  4. Paydar R, Takavar A, Kardan MR, Babakhani A, Deevband MR and Saber S. 2012. Patient effective dose evaluation for chest X-ray examination in three digital radiography centers. Iran. J. Radiat. Res. 10(3-4):139-143.
  5. Wall BF and Hart D. 1997. Revised radiation doses for typical X-ray examinations. Report on a recent review of doses to patients from medical X-ray examinations in the UK by NRPB. Brit. j. radiol. 70(833):437-439. https://doi.org/10.1259/bjr.70.833.9227222